US4097331A - Coolant mass flow equalizer for nuclear fuel - Google Patents

Coolant mass flow equalizer for nuclear fuel Download PDF

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Publication number
US4097331A
US4097331A US05/646,010 US64601076A US4097331A US 4097331 A US4097331 A US 4097331A US 64601076 A US64601076 A US 64601076A US 4097331 A US4097331 A US 4097331A
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United States
Prior art keywords
liner
portions
fuel
duct
inwardly displaced
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Expired - Lifetime
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US05/646,010
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English (en)
Inventor
Paul R. Betten
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US Department of Energy
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US Department of Energy
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Priority to US05/646,010 priority Critical patent/US4097331A/en
Priority to DE2653250A priority patent/DE2653250C3/de
Priority to FR7639758A priority patent/FR2337406A1/fr
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Publication of US4097331A publication Critical patent/US4097331A/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/322—Means to influence the coolant flow through or around the bundles
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/336—Spacer elements for fuel rods in the bundle
    • G21C3/338—Helicoidal spacer elements
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to improving the temperature profile across a fluid cooled subassembly and to accommodating differential growth of components of such a fluid cooled subassembly. More specifically, this invention is directed to a fuel assembly for a nuclear reactor, and specifically a liquid metal cooled fast breeder reactor, characterized by improved coolant mass flow distribution and close fitting of fuel assembly components over the operational life thereof. Accordingly, the general objects of the present invention are to provide novel and improved methods and apparatus of such character.
  • liquid metal fast breeder reactors While not limited thereto in its utility, the present invention is particularly well suited for utilization in liquid metal fast breeder reactors (LMFBR).
  • LMFBR liquid metal fast breeder reactors
  • Liquid metal cooled breeder reactors may offer a partial solution to the problems of fossil fuel shortages and overall rapidly escalating energy costs and such reactors are thus attracting considerable interest and study.
  • LMFBR liquid metal fast breeder reactors
  • LMFBR liquid metal fast breeder reactors
  • Fast breeder reactors which have previously been designed include a plurality of fuel assemblies. Each of these fuel assemblies comprises a bundle of elongated fuel rods mounted within a coolant duct. The fuel rods are spaced from one another and are substantially parallelly arranged. A coolant, typically liquid sodium, will be casued to flow through the duct and through the spaces or sub-channels between the parallel fuel rods and between the fuel rods of the outer row and the walls of the duct. Heat will be transferred from the fuel rod cladding to the coolant and energy produced by the fission reaction will thus be delivered to suitable equipment for utilization.
  • the fuel rod cladding must have a reasonably low neutron cross-section while providing adequate containment of the fuel and fission products at the operational temperatures encountered.
  • a recognized problem in the case of LMFBR fuel assemblies resides in the fact that more coolant flow tends to occur in the peripheral sub-channels; i.e., between the outer row of fuel rods and the coolant duct of each fuel assembly; than in the center or interior sub-channels.
  • This uneven mass flow distribution results in less coolant flow and turbulent mixing for the interior sub-channels which, in turn, causes the fuel rods which define these interior sub-channels to operate at higher temperatures. It is, of course, desired that the reactor be operated at the highest temperature consistent with insuring that the cladding of the "hottest" fuel rod is not subjected to a temperature which could cause melting and rupture thereof.
  • the helically wound wire wrap spacers provide a higher degree of fluid mixing and a lower fluid pressure drop than would be achieved employing spacer grids of the types commonly utilized in pressurized water reactors.
  • the wire wrap does not necessarily improve the mixing or distribution between the interior and peripheral sub-channels of each fuel assembly and there still exists a large difference between the mass flows of the interior and peripheral coolant flow subchannels.
  • the wire wrap design has the advantages of providing accurate spacing between adjacent fuel rods, a lower coolant pressure drop and a more continuous fluid mixing along the length of the fuel assembly.
  • a LMFBR fuel assembly which employs a wire wrap design, reference may be had to U.S. Pat. No. 3,677,893.
  • the wire wrap design will not of itself provide the desired optimum mass flow and temperature distrubution between the peripheral and interior coolant flow sub-channels and previous attempts to overcome these mass flow distrubution problems, for example through the addition of a second wire wrap which completely encloses the outer row of fuel rods of each fuel assembly, have failed to completely overcome the mass flow distribution problem and have introduced an undesirable added degree of complexity to the design and fabrication of the fuel assembly.
  • the materials employed as cladding for the fuel rods of LMFBR's, type 316 stainless steel for example experience swelling at temperatures above about 650° F subsequent to irradiation with fast neutrons for a substantial length of time.
  • differential irradiation induced growth between the fuel rods, wire wraps and fuel assembly duct walls It has been standard practice in the prior art to accommodate this swelling and irradiation induced growth by initially relaxing the system tolerances; i.e., by building a certain amount of "slop" into the fuel assembly.
  • the accommodation of differential growth and swelling must be accomplished in a manner which will not contribute to fuel rod cladding failure.
  • a fuel assembly liner in accordance with the invention includes portions; i.e., corrugations; which are bent inwardly with respect to the remainder of the liner in accordance with a repetitive pattern determined by the pitch of spiral wire wraps on the fuel assembly fuel rods.
  • the inwardly bent liner portions correspond with regions where the wire wrap on the peripheral fuel rods is disposed generally away from the liner thus permitting a reduction in clearance between the liner and the peripheral fuel rods in these regions.
  • the reduction in clearance enhances coolant flow in the interior sub-channels of the fuel assembly at the expense of coolant flow in the peripheral sub-channels and thus provides an improved coolant temperature profile.
  • the fuel assembly liner in accordance with the present invention may also be provided with projections which extend outwardly from those alternate portions of the liner which are not deflected inwardly; such projections contacting the inner wall of the fuel assembly coolant duct. These projections will function as springs and thus will compress or flatten out in response to irradiation induced swelling or differential growth of fuel assembly components whereby new growth of such components will be accommodated.
  • the liner may be closed on itself either by welding or these edges may be joined by means of duct liner springs. These duct liner springs, if present, will accommodate growth by permitting the entire liner to expand.
  • FIG. 1 is a cross-sectional top view of a hexagonal fuel assembly of the type with which the present invention may be employed;
  • FIG. 2 is a partial plan view, prior to assembly, of a fuel assembly coolant duct liner in accordance with a first embodiment of the present invention
  • FIG. 3 is a partial cross-sectional side elevation view of a fuel assembly employing the liner of FIG. 2;
  • FIG. 4 is a partial cross-sectional top view of a fuel assembly employing the liner of FIG. 2;
  • FIG. 5 is a partial side elevation view, before assembly, of a fuel assembly coolant duct liner in accordance with a second embodiment of the invention.
  • Fuel assembly 10 would, in the reactor core, be associated wth a pluraltiy of identical additional fuel assemblies.
  • Fuel assembly 10 includes a continuous outer shroud or coolant duct defining member 12. Uniformly spaced within duct 12, which may be comprised of stainless steel, are a pluraltiy of fuel rods 14.
  • Fuel rods 14, which are also known in the art as fuel elements or fuel pins, are circular in cross-section, elongated and will typically be provided with an external cladding of stainless steel which provides for the containment of the fissionable fuel.
  • Fuel rods 14 are oriented in a spaced parallel relationship and the spacing between adjacent rods is determined and maintained by helical wire wraps 16; the wire wraps also typically being comprised of stainless steel and being individually associated with each fuel rod as is conventional prior art practice.
  • Fuel assembly 10 also includes, between the outer row of fuel rods 14 and the inside of duct 12, a liner 18.
  • the present invention resides in a novel liner 18 which achieves the above described objectives of accommodating swelling and irradiation induced growth while simultaneously assisting in promoting proper coolant mass flow distrubution in the fuel assembly.
  • the liner 18 is shown subsequent to stamping, to define the requisite contour, but prior to folding into the hexagonal shape commensurate with the fuel assembly configuration defined by duct 12.
  • the liner 18 is stamped to provide alternate portions which extend inwardly towards the fuel rods.
  • each of the portions of each side of the liner intermediate the inwardly bent portions for example portions 24 of a first side of the liner and portions 26 of a second side of the liner, are provided with outwardly extending dimples or ridges as indicated respectively at 28 and 30.
  • these dimples or ridges 28 extend in the opposite direction from the "normal" plane of the liner when compared to the inwardly deflected inner portions 20, 22, etc. and the dimples 28 contact the inner wall of duct 12 thus determining the initial positioning of the liner with respect to duct 12.
  • the inwardly bent portions of the liner are positioned such that these portions occur in regions where the wire wrap 16 on the fuel rods spirals inwardly away from the liner.
  • This arrangement may be clearly seen from FIG. 3 and results in minimizing the clearance between liner 18 and the fuel rods of the outer row; the areas of reduced clearance being in an alternating pattern defined by the pitch of the wire wrap.
  • the reduction in clearance allowed by the inwardly bent portions of liner 18; i.e., the raised metal surfaces of the inner wall of the hexagonal liner; provides a frictional barrier to coolant flow in the peripheral sub-channels of the fuel assembly.
  • the net effect is that there will be more coolant flow in the interior sub-channels and less in the peripheral sub-channels and this result, in turn, provides an improved coolant temperature profile.
  • the diversion of coolant from the peripheral sub-channels to the interior sub-channels also results in more interchannel turbulence and mixing.
  • the diversion of coolant from the peripheral to the interior sub-channels is enhanced by the steering effect of the inclined leading and trailing edges of each inwardly bent portion of liner 18; the inclined edges being clearly shown in FIG. 2. From FIG. 3 it may also be seen that in the region where the wire wraps 16 spiral to the outside; i.e. the wraps are on the side of the fuel rods of the outer row disposed toward the liner 18; with the exception of the formation of the outwardly extending dimples 28 the liner is undeflected.
  • Swelling or differential growth is accommodated, in the embodiment of FIGS. 2-4, by compression or flattening of the ridges 28, 30, etc.; i.e., the ridges function as springs which contact the inner wall of duct 12. Swelling may also be accommodated by deformation of the entire liner in accordance with the alternative of FIG. 4. In FIG. 4 the abutting edges of the liner where it closes on itself are not welded together but rather are interconnected by means of a plurality of springs; one spring 32 being depicted in the drawing. As the fuel pins swell the duct liner springs 30 elongate to accommodate the new growth.
  • springs 30 may not be required for operation and swelling and differential growth may be accommodated solely by the flattening of the ridges 28, 30, etc.
  • the use of the liner with the compressible ridges and/or the inclusion of the duct liner springs 32 permits a significant reduction in fabrication cost since the liner absorbs the loose tolerances which were previously required in order to accommodate swelling and differential growth.
  • FIG. 4 depicts a typical fuel assembly wherein there are six fuel rods in the outer periphery or row of the fuel assembly along each side of the fuel assembly.
  • FIG. 4 is a view taken along line 4--4 of the liner of FIG. 2 subsequent to that liner being folded on itself and incorporated into the fuel assembly.
  • FIG. 5 a second embodiment of a liner is depicted in the same unassembled form as shown in the case of the liner of FIG. 2.
  • the liner of FIG. 5 differs from that of FIG. 2 in that the inwardly bent portions 34 of each vertical section or side are vertically offset in stepwise fashion proceeding around the liner.
  • the inwardly bent portions of the liner of the FIG. 5 embodiment have generally horizontal leading and trailing edges rather than the inclined leading and trailing edges which characterize the FIG. 2 embodiment.
  • the liner of FIG. 5 may also be provided with the ridges 28 which function as springs for accommodating swelling and differential growth.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
US05/646,010 1976-01-02 1976-01-02 Coolant mass flow equalizer for nuclear fuel Expired - Lifetime US4097331A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
US05/646,010 US4097331A (en) 1976-01-02 1976-01-02 Coolant mass flow equalizer for nuclear fuel
DE2653250A DE2653250C3 (de) 1976-01-02 1976-11-24 Kernbrennstoffelement
FR7639758A FR2337406A1 (fr) 1976-01-02 1976-12-31 Assemblage combustible nucleaire

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/646,010 US4097331A (en) 1976-01-02 1976-01-02 Coolant mass flow equalizer for nuclear fuel

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US4097331A true US4097331A (en) 1978-06-27

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DE (1) DE2653250C3 (enrdf_load_html_response)
FR (1) FR2337406A1 (enrdf_load_html_response)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4678625A (en) * 1985-08-05 1987-07-07 Westinghouse Electric Corp. Method of straightening bowed irradiated fuel assemblies
US5186890A (en) * 1990-03-02 1993-02-16 Hitachi, Ltd. Reactor core of fast breeder reactor, components of same, and regulating method of coolant distribution of same
US6088420A (en) * 1997-05-09 2000-07-11 Kabushiki Kaisha Toshiba Reactor core
US20100303194A1 (en) * 2009-05-27 2010-12-02 Institute Of Nuclear Energy Research Atomic Energy Council, Executive Yuan Nuclear fuel arrangement in fuel pools for nuclear power plant
US7940883B1 (en) * 2005-12-27 2011-05-10 Kabushiki Kaisha Toshiba Fuel assembly
US11289210B2 (en) * 2012-12-28 2022-03-29 Terrapower, Llc Method of making a nuclear reactor fuel duct

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4420458A (en) * 1981-04-29 1983-12-13 General Electric Company Nuclear fuel assembly with coolant conducting tube

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3150057A (en) * 1962-05-29 1964-09-22 Harry O Monson Fuel subassembly for nuclear reactor
US3607642A (en) * 1968-11-26 1971-09-21 Gen Electric Nuclear reactor fuel assembly
US3677893A (en) * 1971-10-29 1972-07-18 Atomic Energy Commission Fuel assembly for a liquid-metal-cooled fast breeder reactor
US3702803A (en) * 1971-02-12 1972-11-14 Atomic Energy Commission Fuel assembly for a fast reactor
US3767525A (en) * 1972-10-06 1973-10-23 Atomic Energy Commission Irradiation subassembly
US3930940A (en) * 1969-12-12 1976-01-06 Commissariat A L'energie Atomique Nuclear fuel subassembly

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3150057A (en) * 1962-05-29 1964-09-22 Harry O Monson Fuel subassembly for nuclear reactor
US3607642A (en) * 1968-11-26 1971-09-21 Gen Electric Nuclear reactor fuel assembly
US3930940A (en) * 1969-12-12 1976-01-06 Commissariat A L'energie Atomique Nuclear fuel subassembly
US3702803A (en) * 1971-02-12 1972-11-14 Atomic Energy Commission Fuel assembly for a fast reactor
US3677893A (en) * 1971-10-29 1972-07-18 Atomic Energy Commission Fuel assembly for a liquid-metal-cooled fast breeder reactor
US3767525A (en) * 1972-10-06 1973-10-23 Atomic Energy Commission Irradiation subassembly

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4678625A (en) * 1985-08-05 1987-07-07 Westinghouse Electric Corp. Method of straightening bowed irradiated fuel assemblies
US5186890A (en) * 1990-03-02 1993-02-16 Hitachi, Ltd. Reactor core of fast breeder reactor, components of same, and regulating method of coolant distribution of same
US6088420A (en) * 1997-05-09 2000-07-11 Kabushiki Kaisha Toshiba Reactor core
US7940883B1 (en) * 2005-12-27 2011-05-10 Kabushiki Kaisha Toshiba Fuel assembly
US20110110485A1 (en) * 2005-12-27 2011-05-12 Kabushiki Kaisha Toshiba Fuel assembly
US20100303194A1 (en) * 2009-05-27 2010-12-02 Institute Of Nuclear Energy Research Atomic Energy Council, Executive Yuan Nuclear fuel arrangement in fuel pools for nuclear power plant
US11289210B2 (en) * 2012-12-28 2022-03-29 Terrapower, Llc Method of making a nuclear reactor fuel duct

Also Published As

Publication number Publication date
FR2337406B1 (enrdf_load_html_response) 1979-03-23
FR2337406A1 (fr) 1977-07-29
DE2653250A1 (de) 1977-07-14
DE2653250B2 (de) 1978-05-11
DE2653250C3 (de) 1979-02-01

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